ML033290447
| ML033290447 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/21/2003 |
| From: | Dunlap K Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAM-105 | |
| Download: ML033290447 (21) | |
Text
NM' Committed to Nuclear Excellene, DAEC EMERGENCY PLANNING DEPARTMENT PROCEDURE TRANSMITTAL ACKNOWLEDGEMENT MEMO (TAM-105)
To:
NRC-NRR Document Control Desk US NRC Washington DC 20555 Re:
Entire EPIP Document (Copy 28)
PSM
Title:
n/a Distribution Date:
Effective Date of Change:
Return by:
11 / 14 / 2003 11/21/2003 12/05/2003 Please perform the following to your assigned manual. If you have any questions regarding this TAM please contact Don A. Johnson at 319-851-7872.
REMOVE Rev. 145 EPIP Table of Contents Revision EPIP 1.1 (PWR: 23169)
Rev. 21 INSERT Rev. 146 Rev. 22 Rev. 5 Rev. 5 EPIP EAL-01 (PWR: 23187)
Rev. 4 EPIP EAL-03 (PWR: 21938)
Rev. 4 PERFORMED BY:
Print Name Sign Name Date Please return to:
K. Dunlap PSC/Emergency Planning 3313 DAEC Rd.
Palo, IA 52324 To be completed by DAEC EP personnel only:
Date TAM returned:
EPTools updated:
114CM5 Page 1 of 1
Committed to Nuclear Excellenc Duane Arnold Energy Center Operated by Nuclear Management Company, LLC Friday, November 14, 2003 NRC-NRR Document Control Desk US NRC Washington, DC 20555 To: NRC-NRR Document Control Desk From: DAEC Emergency Planning Department Re: Description of changes to the following documents EPIP 1.1 Determination of Emergency Action Level Add more information re: EAL Operating modes. Remove requirement to reference the EAL Bases Document for every EAL declaration.
EPIP EAL-01 Abnormal Rad Levels/Radioactive Effluent EAL Table Remove reference to a telemetered perimeter rad monitoring system. Define 200xODAM limit.
EPIP EAL-03 Hazards and Other Conditions Affecting Plant Safety EAL Table Various changes to ensure consistency with the EAL Bases Document and NEI 99-01 revision 4.
Please contact Paul Sullivan, Manager of Emergency Preparedness at DAEC, (319)851-7191, if you require further information.
3313 DAEC Road - Palo, Iowa 52324-9785 Telephone: 319.851.7191 - Fax: 319.851.7364
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, EMERGENCY PLAN IMPLEMENTING PROCEDURES': 4 INDEX
,PAGE 1 of 7 Procedure Title Revision Date Number 1.1 Determination of Emergency Action Levels 22 11/21/03 1.2 Notification 29 10/13/03; 1.3; Plant Assembly and Site Evacuation 9
09/12/01 1.4-Release of Emergency-Related Information 5'
10/13/03 1.5 Activation and Operation of the EOF 5
10/13/03
'2.1 Activation'and Operation of the OSC 14 10/13/03 2.2----
Activation and Operation of the TSC 24 10/13/03
-2.3 Operation of the FTS-2001 Phone Network-7 10/13/03 2.4 Activation and Operation of the ORAA-8 09/12/01 2.5 Control Room Emergency Res'ponse Operation' 15 10113/03 2.6 Activation and Operation of the ORAL 9
12/30/02 2.7, Activation and Operation of the ODEF 6
10/15/01 2.8 Security Threat 2
7/30/03 3.1 In-Plant Radiological Monitoring 13 10/13/03 3.2.
Field Radiological Monitoring 14 10/13/03 3.3 Dose-Assessment and Protectiv'e Action 20 10/13/03 4.2 First Aid, Decontamination and Medical Support 7
8/23/02 4.3 Rescue and Emergency Repair Work.;
11 8/23/02 4.5 Administration of Potassium Iodide (KI) '
7 2/10/03 5.2 '
Recovery and Re-entry 10 10/13/03' I
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`EMERGENCY PLAN IMPLEMENTING PROCEDURES< Rv.14 9
L
~~~~~~~~~~~~Rev.
146 INDEX PAGE 2 of 7 Form Title Revision Referencing Number Number Procedure
-CR-01 OSM/OSS Checklist Rev. 4 EPIP 2.5 CR-03 Dose Projection & ARM Data Sheet Rev. 0 EPIP 2.5 CR-04 Control Room to TSC Transfer Checklist Rev. 2 EPIP 2.5 EAL-01 Abnornal Rad Levels/Radioactive Effluent Table Rev. 5 EPIP 1.1-EAL-02 Fission Barrier Table Rev. 4 EPIP 1.1 EAL-03 Hazards & Other Conditions Affecting Plant Safety Rev. 5 EPIP 1.1 EAL-04 System Malfimction Table Rev. 4 EPIP 1.1 EAL-05 ISFSI Table Rev. 0 EPIP 1.1 EOF -02 NRC - HPN Communicator Checklist Rev. 3 EPIP 1.5 EOF - 03 Technical Recorder Checklist Rev. 2 EPIP 1.5 EOF -04 Summary of Computer Data Backup Collection Rev. 2 EPIP 1.5 Activities EOF - 05 EOF Information Services Representative Checklist Rev. 3 EPIP 1.5 EOF -06 DAEC Key Parameter Log Rev. 0 EPIP 1.5 EOF -07 Emergency Response and Recovery Director Rev. 5 EPIP 1.5 Checklist EOF -'08 Rad & EOF Manager Checklist Rev. 7 EPIP 1.5, 3.3 EOF - 09 EOF OPS Liaison Checklist Rev. I EPIP 1.5 EOF -10 EOF-Communicator Checklist Rev. 3 EPIP 1.5 EOF-11 Support Services Coordinator Checklist Rev. 3 EPIP 1.5 EOF-12 Field Team Director Checklist Rev. I EPIP 1.5, 3.3 I
,?-E ERGEN -;Y P.1AMPLCME IG P.ROCEDURESi5 'Rev 146-INDE)C PAGE 3 of 7 EOF EOF MIDAS Operator Checklist Rev. 1 EPIP 1.5,3.3 EOF Radiological Data Plotter Checklist Rev. 0 ;
EPIP 1.5,3.3 EOF-16 Radiolo'gical Assessment Coordinator Checklist Rev. 2 EPIP 1.5,3.3' EOF - 17 EOF-Security Access Clerk Checklist Rev. 3 EPIP 1.5, EOF -18
-EOF Staffing Accountability Roster Rev. 4 EPIP 1.5 EOF 19 Drill Announcement Message Rev.-0 EPIP-1.4,1.5 EOF - 20 Emergency Announcement Message Rev. 1
'EPIP 1.4,1.5 EOF - 21 Personnel Access Log Rev.1 EPIP 1.4, 1.5 EOFi-22 Registration Form Rev. 0 EPIP 14,1.5 EOF-23 Security'PostLog Rev. 2 EPIP 1.4,1.5 EOF - 24 _ First Floor Security Post Description' Rev.2 EPIP1.,1.5 EOF -25 Fourteenth Floor Security Post Description Rev. 11 EPIP 1.5 EOF -27
- Status Update Message - EOF Communicator Rev. 0 EPIP 1.5.
EOF -28 Verbal Closeout Summary Rev. 0 EPIP 1.5 EOP-' 29 Written-Closeout Summary Rev. 0 EPIP 1.5 EOF-'30 Status Board Rev. 1 EPIP 1.5 EOF-31 Access B adge Example Rev. 0 EPIP 1.5 EOF - 32 EOF Staff Response Rev. 4-EPIP..15:-
EOF - 33 Recovery Issues Rev.0, EPIP 5.2 EOF -34 EOF Activities Rev.0-EPIP 5.2 EOF-735 Recovery Phase Plan Outline Guidance
- ,-Rev.0
' EPIP.52 EOF -36 RE-Entry Briefing Guide Rev.0.
EPIP 5.2
'OFO -37 RE-Entry Debriefing Guide Rev. 0 EPIP 5.2 EOF 38 EOF Messenger Checklist Rev.1 EPIP 1.5 ERO' 01 ERO Position Equivalency Table Rev. 1 EPIP 1.5" JPIC - 01 JPIC Manager Checklist Rev.4 EPIP 1.4' JPIC 03 Alliant Spokesperson Checklist Rev. 3 EPIP 1.4 I
V)
EMERGENCY PLAN IMPLERvENTINGROCEDURES' R.
146 INDEX PAGE 4 of 7 I
JPIC - 04 Technical Liaison Checklist Rev. 4 EPIP 1.4 JPIC - 05 Sequence of Events Rev. 0 EPIP 1.4 JPIC - 06 Public Information Officer Support Checklist Rev. 5 EPIP 1.4 JPIC -07 Logistics Coordinator Checklist Rev. 4 EPIP 1.4 JPIC - 08 Logistics Support Checklist Rev. 4 EPIP 1.4 JPIC - 09 Audiovisual Support Checklist Rev. 4 EPIP 1.4 JPIC - 11 Rumor Control Coordinator I Checklist Rev. 3 EPIP 1.4 JPIC - 12 Rumor Control Event Summary Log Rev. 1 EPIP 1.4 JPIC - 13 Rumor Control Coordinator II Checklist Rev. 2 EPIP 1.4 JPIC - 14 Public Rumor Control Checklist Rev. 2 EPIP 1.4 JPIC - 15 News Media Rumor Control Checklist Rev. 4 EPIP 1.4 JPIC - 16 Assistant JPIC Manager Checklist Rev. 3 EPIP 1.4 JPIC - 17 JPIC Security Access Control Checklist.
3 EPIP 1.4 JPIC - 18 Sixth Floor Security Post Description Rev. 2 EPIP 1.4 JPIC - 19 JPIC Distribution List Rev. 2 EPIP 1.4 NOTE-01 ERO Notification -Phone System Callout Rev. 5 EPIP 1.2 NOTE-02 ERO Notification - Alphanumeric Paging System Rev. 3 EPIP 1.2 Callout NOTE-03 Event Notification Worksheet Rev. I EPIP 1.2 NOTE-04 Plant Assembly Notification Rev. 2 EPIP 1.2 NOTE-05 Emergency Action Level Notification Rev. 7 EPIP 1.2 NOTE-06 Plant Page for Emergency Classification Changes Rev. I EPIP 1.2 NOTE-07 Basic Notification Flowpath Rev. 2 EPIP 1.2 ODEF-01 ODEF Decontamination Waiting Area Rev. 0 EPIP 2.7 ODEF-02 Floor Plan for ORALJODEF Rev. 0 EPIP 2.7 ODEF-03 Travel Route to ORAL/ODEF Rev. 0 EPIP 2.7 ODEF-04 12 th Avenue Entrance to ORAIJODEF Rev. 0 EPIP 2.7 ORAA-01 Offsite Relocation and Assembly Area Supervisor's Rev. I EPIP 2.4
- EMERGENCY PLAN'IMPLEMENTING PRO¢ED'RES ROCEDURESRev.'146 I
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,, -,,INDEX PAGE 5 of 7 I
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Checklist,.
ORAA-02 Health Physics Support for the Offsite Relocation, Rev. 0 EPIP 2.4
-and Assembly Area ORAA-03
-Security Support for the Offsite Relocation and Rev. 0 EPIP 2.4
,__,,__Assembly Area ORAA-'04 Offsite Relocation and Assembly Area Rev. 0 EPIP 2.4 ORAA-05 Offsite Relocation and Assembly Area Parking and Rev. 0' EPIP 2.4 Vehicle Mom nitng OSC-01 OSC Layout Rev. 0 EPIP 2.1 OSC-03, Minimum Staffing Level Rev.,
EPIP 2.1
-OSC-04 Recommended Log Entry Topics Rev. 0 EPIP 2.1 OSC-05' Emergency Event Log Sheet Rev. 0 EPIP 2.1 OSC-06' Personal Statement Concerning Incident Rev. 0 EPIP 2.1 OSC-07 Emergency'Exposu're Tracking Log Rev. 0 EPIP 2.1 OSC-08 OSC Supervisor Checklist
,Rev.
0 EPIP.2.1 OSC-09 Health Physics'Supeervisor Checklist
,;Rev. 0 EPIP 2.1 OSC-10,
IC/EM & Mech'anical Supervisor Checklist Rev.- I EPIP 2.1 OSC-11 Emergency Assignhient Staffing Board Duties ;
Rev. 0 EPIP 2.1 OSC-12 External Exposure Limits
'Rev. 0.
EPIP 4.3 OSC-13
'Guidance on Dose Limits for Workers Performing:'
- Rev. 0 EPIP 4.3 Emergency Services OSC-14_,,
Guidelines Regarding Selection of Volunteers ---
Rev 0 -
EPIP 4.3 OSC-15 05C Repair Team Work Order..
Rev. 0 EPIP 4.3 OSC-16. '
Repair Team Datasheet Flowpath
--- Rev. 0
-EPIP 4.3 OSC-17, Field Monitoring Team Checklist
-Rev. 0 EPIP 2.1 PAR 01 PAR Decision Making - Recommendations Rev. 0 EPIP 3.3 PAR'- 02 PAR Decision Making - Flowchart Rev. 0, EPIP 3.3 PASE-02 Onsite Assembly Locations' -
Rev. 2 EPIP 1.3 PASE-05 Site Evacuation Routes Rev..l I EPIP -1.3
[>BtEMERGENC.Y! PLAN IMPLEMENTING P. ROCEDU*R~sEP RE v14 EMERGENCY I~~~~z Rev. 146 I
11
I INDEX I PAGE 6 of 7 INDEX PAGE6 of 7~~~~~~~~~~~~~~~~~~~~~~~~
SAM-0 1 EOP-SAG Transition Checklist Rev. 0 EPIP 2.2 TSC-01 Emergency Coordinator Checklist Rev. 4 EPIP 2.2 TSC-02 TSC-EOF Transfer Checklist Rev. 3 EPIP 2.2 TSC-03 Site Radiation Protection Coordinator Checklist Rev. 2 EPIP 2.2 TSC-04 Technical & Engineering Supervisor Checklist Rev. 4 EPIP 2.2 TSC-05 Quality Assurance Checklist Rev. 1 EPIP 2.2 TSC-06 Security & Support Supervisor Checklist Rev. 2 EPIP 2.2 TSC-07 Administrative Supervisor Checklist Rev. 2 EPIP 2.2 TSC-08 Material Management Supervisor Checklist Rev. 2 EPIP 2.2 TSC-09 TSC Communicator Checklist Rev. 2 EPIP 2.2 TSC-1 0 CR-Communicator Checklist Rev. 4 EPIP 2.2 TSC-12 ENS Communicator Checklist Rev. 2 EPIP 2.2 TSC-13 HPN Communicator Checklist Rev. 1 EPIP 2.2 TSC-14 TSC/OSC Operations Liaison Checklist Rev. 2 EPIP 2.2 TSC-15 Radiological Support Staff Checklist Rev. 2 EPIP 2.2 TSC-18 TSC MIDAS Operator Checklist Rev. 0 EPIP 2.2 TSC-19 Technical & Analysis Engineer Checklist Rev. 2 EPIP 2.2 TSC-20 TSC Operations Supervisor Rev. 3 EPIP 2.2 TSC-21 Electrical Engineer Checklist Rev. I EPIP 2.2 TSC-23 Mechanical Engineer Checklist Rev. 0 EPIP 2.2 TSC-24 Reactor Engineer Checklist Rev. 2 EPIP 2.2 TSC-26 Information Services Representative Checklist Rev. 2 EPIP 2.2 TSC-27 Fire Marshall Checklist Rev. I EPIP 2.2 TSC-28 NRC Roles During A Nuclear Power Plant Rev. 0 EPIP 2.2 Emergency Checklist TSC-29 TSC Minimum Staffing Level Rev. 3 EPIP 2.2 TSC-30 Emergency Action Request Log Rev. 0 EPIP 2.2 TSC-3 1 Radio Operator Log Rev. I EPIP 2.2
':iEMERGENCY.~~PLAN'.IMPLEMENTING~PROCEDURES.
Rev. 146 U
~~~~~~~~INDE)C PAGE 7 of 7 TSC-33 Typical Organization of the NRC Site Tearn Rev. 0 EPIP 2.2 TSC-34 TSC Organization Chart Rev. 4 EPIP 2.2 TSC-35 Assignment Forn Rev. 0 EPIP 5.2 TSC-36 Deactivation Report Rev. 0 EPIP 5.2 TSC-37 Plant Operations Status Rev. 0 EPIP 5.2 TSC-38 TSC/Control Roomi/OSC Activities Rev. 0 EPIP 5.2 TSC-39 TSC Clerical Checklist Rev. 0 EPIP 2.2 TSC-40 ARM Locations Rev. 0 EPIP 3.1/4.3 TSC-41 PASS Capabilities Rev. 0 EPIP 3.1 TSC42 On-Site Map Rev. 0 EPIP 3.2 TSC-43 ESB Logon Instructions (TSC/CRIEOF)
Rev. 0 EPIP 2.2 I
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-. EMERGENCY.PLAN:IMPLEMENTING.PROCEDURE EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS Page 1 of 10 Usage Level REFERENCE lEffective Date: 11ti( l(
rTECHNICAL REVIEW Prepared and Date:
Verified by:
a07 5
_3 Validated by:..
g
=
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Date: //5o3 E Trgency lanning Staff PROCEDURE APPROVAL I am responsible for the technical content of this procedure.
Approved by:
Date:
o3 Man er, Emergency lanning
EMERGENCY PLAN IMPLEMENTING PROCEDURE-;
EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS Page 2 of 10 Table of Contents Paqe 1.0 PURPOSE..................
3 2.0 DEFINITIONS..............................................................................................3 3.0 INSTRUCTIONS 5
3.1 OVERVIEW
.5 3.2 EVENT CLASSIFICATION
.6 3.3 CRITERIA FOR EMERGENCY CLASSIFICATION CHANGES
.8 4.0 RECORDS 9
5.0 REFERENCES
9 6.0 EPIP FORMS 10
,..-.-;-;:EMERGENCY PLAN IMPLEMENTING PROCEDURE - ;
- EPIP 1.1:
Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS Page 3 of 10 1.0 PURPOSE (1) Provides guidance to the Operations Shift Manager'(OSM), Emergency Coordinator (EC), or Emergency Response and Recovery Director (ER&RD),
as applicable, when determining a need to declare or retract an emergency
' event at DAEC.
- 2.0 DEFINITIONS
.-,~~~~.
.0
'-(1) Emergency Action Level (EAL)
(a) -A pre-determined,' site-specific, observable threshold for a plant Initiating
'- Condition that places the plant in a given Emergency Classification Level.
-An EAL can be: an instrurm'ent reading, an equipment status indicator, a measurable parameter (on-site or off-site), a discrete observable event, results of analyses, entry into specific emergency operating procedures, or another phenomenon which, if it occurs, indicates entry into a particular Emergency Classification Level.'
(2) EAL Technical Basis Document
.,(a)
This document was developed to:
(i) Provide clear documentation of how NEI generic guidance was applied in the development of DAEC upgraded EALs.
(ii) Provide justification of any exceptions or additions to NEI generic guidance as it is applied to DAEC.
(iii) Facilitate the regulatory approval of the upgraded EALs that is required under 1 OCFR50 Appendix E.
(3) Emergency Classification Level (a) These are taken from 1 OCFR50 Appendix E. They are, in escalating order:
(i) (Notification of) Unusual Event (UE): Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plantlISFSI. No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS Page 4 of 10 (ii) Alert: Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plantIISFSI. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
(iii) Site Area Emergency (SAE): Events are in progress or have occurred which involve an actual or likely major failure of plant functions needed for the protection of the public. Any release is not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.
(iv) General Emergency (GE): Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting, with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Guideline exposure levels offsite for more that the immediate site area.
(4)
ISFSI (a)
Independent Spent Fuel Storage Installation facility and associated cask loading and storage activities.
(5) Retraction (a) The recanting of an Emergency Action Level that was declared due to an indeterminate condition.
'^29EMERGENCY PLAN!IMPLEMENTING PROCEDURE-EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS Page 5 of 10 3.0 INSTRUCTIONS 3.1 OVERVIEW (1) The Control Room, TSC, and EOF staff shall evaluate plant/ISFSI conditions to determine whether any EAL Threshold Values have been met. The OSM/EC/ER&RD should declare the appropriate EAL within 15 minutes once indications are available that the Threshold Value for an EAL has been K exceeded.
NOTE For the purpose of making EAL determinations it is acceptable to use SPDS or ERDS information.- It is always prudent to verify the SPDS.- or -ERDS 'information with redundant instrumentation, when it is available.
(2) The OSM/EC/ER&RD shall ensure requisite notifications are made within the 15-
-;minute requirement, per EPIP 1.2"'Notification'.
(3) Plant assembly and site evacuation decisions shall be made in accordance with.
- EPIP'1.3, 'Plant Assenmbly and Site' Evacuati6n'. '
(4) The EC/OSM/ER&RD shall review and approve the emergency classification to deitermnine if events/conditions have changed that may warrant upgrade, declassification, termination or retraction. '
(5) The EC/OSM/ER&RD shall ensure activation of the Emergency Response Organization is underway/completed, as required.
(6)'if an EAL has been declared due'to an indeterminate condition and subsequent investigation/evaluation discovers the condition' did not exist,.the'even'nt may be retracted. 'Notifications shall be made per EPIP:1.2 'Notification'.
(7) The plant operating mode that existed'at the time that the event occurred,' prior to any protective system or operator action initiated in response to the condition, Is compared to the mode applicability of the EALs: If an event occurs, and a lower or higher plant operating mode is reached before'the emergency' classification can be made, the declaration shall be based on the mode that existed at the time the'event occurred.
KU
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS Page 6 of 10 3.2 EVENT CLASSIFICATION (1)
Emergency conditions are classified in an ascending order of severity as follows:
(a)
NOTIFICATION OF UNUSUAL EVENT (Recognition Category AU, FU, HU, SU, EU)
(b)
ALERT (Recognition Category AA, FA, HA, SA)
(c)
SITE AREA EMERGENCY (Recognition Category AS, FS, HS, SS)
(d) GENERAL EMERGENCY (Recognition Category AG, FG, HG, SG)
(2)
When a suspected emergency condition occurs, the EC/OSM/ER&RD and their associated staff, shall make the initial analysis and determination of the classification, referring to the appropriate EAL tables in Appendix 1 and the EAL Basis Document. The appropriate EAL should be declared within 15 minutes once indications are available that the Threshold Value for an EAL has been exceeded. Appendix 1 of the EPIP's contains the five tables, EAL-01 through EAL-05, covering Emergency Action Levels.
(3)
To determine an EAL: Categorize the general type of event, referring to the EAL tables.
(4)
If the OSM has been fulfilling the responsibilities of the EC, upon declaring the emergency classification, the event, the time declared and the action(s) taken shall be logged in the Shift Manager's Log.
(5)
Other events not specifically included in this procedure which may be based on plantIISFSI prognosis, weather, or other external events, as well as events that have a high likelihood of occurrence may be classified as a NOTIFICATION OF UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY at the discretion of the EC/OSM/ER&RD. The primary consideration for classification of these events shall be to protect the health and safety of site personnel and the public.
(6)
The highest emergency classification for which an Emergency Action Level (EAL) is CURRENTLY met should be declared.
(a)
If an action level for a higher classification was exceeded, but the situation has been resolved prior to offsite reporting, the higher classification level should be REPORTED to the offsite agencies and the NRC, but SHOULD NOT be declared.
.<-.EMERGENCY-PLAN IMPLEMENTING PROCEDURE.-.o;i EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY-ACTION LEVELS Page 7 of 10 I
(b)
The notification must indicate the CURRENT classification, the period of:
time that the higher classification existed and the mitigating conditions that caused the reduction in the emergency classification..
(7)
Reclassification shall be reviewed and approved by the EC/OSM/ER&RD.
(a)
Reclassification should be based upon the guidance provided in the EAL Tables and Reference 1.
(b)
The EC/OSM should consult with the following personnel, if available, during such evaluations:
(i) Site Radiation Protection Coordinator (SRPC)
(ii) TSC Operations Supervisor
. (iii) Tech and Engineering Supervisor (iv) Emergency Response and Recovery Director (c)
The ER&RD should consult with the following personnel:
(i) Emergency Coordinator (ii) EOF OPS Liaison (d)
The EC/OSM shall ensure that offsite agencies are notified of the
- reclassification in accordance with EPIP 1.2, 'Notificatiorn'. If the Emergency Operations Facility (EOF) has been declared operational, the ER&RD shall assume this responsibility, unless otherwise advised.
(e)
If the OSM is fulfilling the responsibilities of the EC, reclassification of an event shall be documented in the Operations Shift Manager's Log or the TSC.Supervisor's Log as appropriate.
(8)
As plantISFSI conditions change, the EC/OSM/ER&RD shall ensure that
.plantISFSI status is monitored and the EAL Tables and EAL Basis Document are constantly consulted in order to adjust the emergency classification, as appropriate. The appropriate EAL should be declared within 15 minutes once indications are available that the Threshold Value for an EAL has been exceeded.;
EMERGENCY PLANF IMPLEMENTING PROCEDUREr, EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS Page 8 of 10 3.3 CRITERIA FOR EMERGENCY CLASSIFICATION CHANGES (1)
As plantIISFSI conditions change, consider:
(a)
The probability that plantIlSFSI conditions will continue to improve.
(b)
The probability that plant/ISFSI conditions might worsen, thereby necessitating upgrading the emergency classification once the emergency has been downgraded.
(c)
The need to staff all or some of the emergency response facilities.
(d)
Evaluating existing conditions with respect to the criteria established for each emergency classification per the EAL Tables.
(e)
The control or termination of non-routine releases of radioactive material to the environment.
(f)
The control or cessation of any fire, flood, earthquake, or similar emergency conditions.
(g)
The specified corrective action has been taken, or the plant has been placed in the appropriate operating mode.
(h)
All required notifications are completed.
(i)
The TSC technical staff has evaluated the plantISFSI status with respect to the Technical Specifications/applicable 1 OCFR 72 Certificate of Compliance requirements and recommends downgrading the emergency classification.
(2)
An emergency condition can be considered resolved, and a Recovery Organization established, if necessary, when the following guidelines have been met or addressed:
(a)
Existing conditions no longer meet the emergency classification criteria and it appears unlikely that conditions will deteriorate further.
(b)
No surveillance relative to offsite protective actions is needed, except for the control of foodstuffs, water, and offsite contamination, or environmental assessment activities.
(c)
Radiation levels in affected in-plant/ISFSI areas are stable or decreasing to acceptable levels.
., I 14%
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<-~-.EMERGENCY PLAN IMPLEMENTING PROCEDURE-.<+
<.-.;EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS.
Page 9 of 10 (d)
Releases of radioactive material to the environment are under control or.
have ceased.
(e)
No Emergency Operating Procedure (EOP) entry condition exists.
(f)
The reactor is in a stable and safe shutdown condition, and long-term core cooling is available as required.
(g)
The control or cessation of any fire, flood, earthquake, or similar emergency conditions. -
(h)
All EAL notifications have been completed.
(i)
Offsite conditions will not limit access of personnel and support resources.
0().
Discussions have been held with the Nuclear Regulatory Commission (NRC), State and local organizations with FEMA input as necessary, and agreement has been reached to terminate the emergency.
(k) - The TSC technical staff has evaluated the plantISFSI status with respect;
- to the Technical Specificationslapplicable 10CFR 72 Certificate of Compliance requirements and concurs with the termination of the emergency.
4.0 RECORDS All logs, forms, and records generated must be forwarded to the EP Department and retained in accordance with QA Record Retention requirements. Authorization for disposal shall be obtained from the NRC.
5.0 REFERENCES
(1) DAEC Emergency Plan (2)
DAEC EAL Technical Basis Document (3)
DAEC Technical Specifications (4)
Emergency Operating Procedures (EOPs)
(5)
Updated Final Safety Analysis Report
EMERGENCY: PLAN IMPLEMENTING PROCEDURE EPIP 1.1 Rev. 22 DETERMINATION OF EMERGENCY ACTION LEVELS Page 10 of 10 (6)
EPIP 1.2, 'Notifications' (7) 1 OCFR50 Appendix E (8) 10CFR 72.32(c) and (d)
(9)
NEI Methodology for Development of Emergency Action Levels NUMARC/NESP-007 NEI 99-01 Revision 4, May 1999/September 2002 (10) NEI Methodology for Development of Emergency Action Levels NUMARC/NESP-007 NEI 97-03 August 1997 6.0 EPIP FORMS TABLE-'
FORM No.
Abnormal Rad Levels/Radioactive Effluent EAL-01 Fission Barrier Table EAL-02 Hazards and Other Conditions Affecting Plant Safety EAL-03 System Malfunction EAL-04 Independent Spent Fuel Storage Installation (ISFSI)
EAL-05